IR 05000020/1990001
| ML20062D657 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 10/31/1990 |
| From: | Alexander Adams, Austin M, Bores R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20062D655 | List: |
| References | |
| 50-020-90-01, 50-20-90-1, NUDOCS 9011150051 | |
| Download: ML20062D657 (17) | |
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U. S. NUCLEAR REGULATORY COMMISSION t
REGION I
Report N /90-01 Docket N m
- License N R-37 Licensee: Massachusetts Institute of Technology J m 138 Albany Street Cambridge, Massachusetts 02139
' Facility Name: MIT Research Reactor
Inspection At: Cambridge, Massachusetts b ' Inspection Conducted:
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September 17-20, 1990
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Inspectors: b(d /C M. A. Austin, Radiation Specialist, Effluents
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Radiation Protection Section (ERPS), Facilities Radiological Safety and Safeguards (FRSSB),
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-Division. of Radiation Safety and Safeguards (DRSS)
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WW A, Adams,9roject Manager, Non-Power Reactor, Decommissioning and-Environmental Project
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~ date Directorate (PDNP); Nuclear Reactor-Regulation (NRR)
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Approved by:
R, J. BoreV, Chief. Effluents Radiation
/$M/M date Protection Section, FRSSB, DRSS Inspection-Summary: _I_nspection'on September 17-20,1990 (Report No. 50-20/90-01)
Areas' Inspected: Routine, unannounced inspection of operations and radiological controls at the MIT.Research Reactor, including: organization, operations < logbooks, safety committees, procedures, and status of previously identified item _ Results: No violations were i n ntified. One Inspector Followup Item was
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identified regarding the adequacy of radiological control procedures (paragraph 8.2).
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o011150051 901104 PDR ADOCK 05000020 g PDC
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DETAILS 1.0 Individuals Contacted M. Austin, Radiation Protection Technician
- Bernard, Director of Reactor Operations B. Graber, Radiation Protection Technician
- K. Kwok, Superintendent of Reactor Operations
- F. Mass (, Director of Radiation Protection Office
- F. McWilliams, Reactor Radiation Protection Officer
- Denotes those present at the exit intervie The inspectors also -
interviewed other licensee employees during the inspectio .0 Organization The facility management organization of the Massachusetts Institute of Technology Re>earch Reactor (MITR) was as described in Technical Specification (TS) Figures 7.1.1 and 7. Although several personnel changes have occurred at the reactor operator level, facility management has not changed since the last inspectio The inspector confirmed that the management responsibilities of TS 7.1 were being carried ou Discussions with the licensee confirmed that the reactor staff qualifications of TS 7.3 were me No violations or deviations were identifie .0 Facility Tour The inspectors toured the facility with the Superintendent of Reactor Operations to visually assess the condition of the facilit The facility appeared to be well-maintained, and hou:ekeeping in the containment was adequat The inspectors noted the licensee effort to quickly identify the source of leaks that might occur in the heavy water system by the use of leak tapes on most of the heavy water system joints in the equipment room. This system would send a signal to the control room if a leak were to occu .0 Reactor Startup At the end of the facility tour the inspectors witnessed a start-up of the reacto The start up was performed in accordance with Procedure PM 2.3, dated November 15, 198 A copy of the procedure was present at the console during start up for operator reference. The start up was performed by a licensed Reactor Operator (RO) under the supervision of the licensed Senior Reactor Operator (SRO). The SRO provided the operator intermediate rod positions at which to pause during the approach to criticality and assisted in the switch-over of instrument channels from start up detectors to power detector . . . . . _ . . _ _ _ .
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The start-up was conducted from a suberitical condition with all control rods full-in to a power level of 500 kW(t). The control rods were 4 individually withdrawn to 4 inches, and.the regulating rod was withdrawn- i to 5 inches where it remained until power was reached. The control rods .
were.then individually withdrawn to-intermediate positions as determined !
by the SRO to observe reactor behavior and detect premature criticalit Criticality was achieved at a control rod position of approximately 9.25 inches withdrawn. This was the predicted estimated critical rod position as determined independently by two operators. Reactor power was increased to 250 kW(t), at which level power was stabilized, the equipment room was- ,
checked, and cooling towers were put in operation in accordance with- ~
Procedure PM 3.1.1.'3. Power was then increased to 500 kW(t) on a 50-second period and then was stabilized. The inspector noted that the operator at the controls monitored the instrumentation with care, and that i the. console had her full attention during reactivity additions. Excellent '
communication was maintained between-the R0 and SRO, and the start-up was !'
conducted in a highly professional manner. No violations or deviations were identifie .0 0_perations Logs -
The inspector' reviewed the Reactor Console Logs for the period October 23,-1989 to September 19, 1990 and the Bypass Logs, which are part of the Reactor Console Logs. The inspector.also reviewed the Instrument / Equipment Malfunction Workbook '(Job Workbook). Information concerning reactor status and events, such as start-up'and shutdown, experiment movement and equipment room entries, were entered in the Reactor. Console Lo'gs. The Bypass Log listed reactor equipment bypasses i and the individuals who approved each bypass, . This log was arranged s that the reactor operator could quickly determine which bypasses were in place. The Job Workbook listed reactor equipment that was in need of
" repair / maintenance along with the status of the repair / maintenance effor .The reactor. operator could quickly determine which instruments and equipment were in need of service. Several entries were selected for _
follow-up to obtain more _information or for clarification. All-entries questioned-were resolved satisfactorily. The inspector noted that in some cases it was not clear from the logs ~why certain events such as alarms occurred or what action was taken to correct the situation. The licensee stated that more attention would be given_to clarifying log entrie No
. violations or deviations were identifie ~
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'6.0 Nuclear Safeguards Committee :
The MIT Reactor Safeguards: Committee (RSC) minutes of the. sixty-eighth meeting on December 20, 1988 and the sixty-ninth meeting on-December 20, 1989 were reviewed by the inspector. The meetinos met the ;
annual meeting frequency requirements of the TS. A quorum as required by '
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TS was present at both meetings, with the reactor staff constituting less ,
I than half of the members present, as also required by T !
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4 i The. inspector noted that'Special ud Standing Subcommittees were l C
authorized by the RSC to review and approve'certain experiments and other '
items. The RSC reviewed the Subcommittee activity, authorizations of the Subcommittees, experimental activity, outstanding items, NRC inspections, changes to the TS and Safety Analysis Report (SAR), the. facility annual report, the emergency exercise, Reportable-Occurrence Raports (ROR), and the results of independent and administrative audits. The inspector ;
noted the RSC has no TS audit. responsibility, No violations or deviations were identifie ,
17.0 Operations Procedures The inspector reviewed the following procedures during the course of the inspectio PM 1.4, " Review and Approval of Plans, Procedures, and Facility -
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Equipment and Changes Thereto" PM 1.8, " Reactor Operations Logs" PM 3.1.1.1, " Mechanical Two Loop Start-up Checklist" PM 3.1.1.2, " Instrumentation Two Loop Start-up Checklist" PM 3.1.1.3, " Cooling Tower Two Loop Start-up Checklist" PM 2.3, " Reactor Start-up Procedures" '
The reviewed procedures appeared adequate to accomplish their purpose, The inspector notpd that there were " pen and ink" changes to PM 3.1. that were up_tc several years old. All changes were initialed by two
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Senior Reactor Operators as required by procedures. .The licensee stated that this procedure was in the process of being retyped and that the pen and ink changes would be permanently incorporated-into the procedure, The inspector;had no further questions. -No violations or deviations were ,
identifie .0 Radiological Controls 8.1 Routine Surveillance The inspector accompanied the radiation protection (RP) technicians and observed their, performance of routine sut veillance activitie The inspector' observed the collection, preparation and analysis of secondary system (cooling tower) water. The secondary system water is routinely analyzed by an intrinsic GeLi detector primarily to identify any N-16, a liquid scintillation detector to detect any H-3,
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- < and a gas proportional counter to determine any gross alpha or beta activity, i
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.The inspector observed.the performance of smear surveys for P_, removable contamination and portable survey instrument measurements for external radiation. Various areas are smeared daily during normal: working hours, and other areas are smeared every three month "
or every six months. The inspector observed that the licensee recorded the results of these smear samples in a Monthly Survey Book or a Daily Survey Book. The inspector observed that the RP technician took several external radiation readings in a given area, then recorded the highest reading obtained for that area. The RP technician also recorded the highest external radiation reading on
'the outside of the envelope containing the smear sample for that area, then later transcribed this measurement value in the
! appropriate logbook in the RP office. No violations or deviations were identifie .2 Program ~ Procedures
'The inspector determined that the licensee'had no procedures that describe how the RP program is actually implemented. The' observed performance of routine RP technicians' duties was based upon oral instructions from the RP Officer to the RP technicians. The current RP Of ficer based his instructions, in large part, upon those which he received from his predecessor. The inspector observed that some
" data sheets"=for various RP tasks, such as activity calculations for gamma spectroscopy results, provided outdated and misleading
'information. For other tasks, such'as the performance of routine external radiation readings, there was no written guidance as to what measurements to take,and what to. record. This lack of procedures
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-could result in an overall RP program-that is inconsistently or- ;
improperly implemente This lack of documentation also made it- '
extremely dif ficult 'to assess the adequacy of the RP program. The inspector stated that this lack of. procedures was a serious concern, which will receive more attention-during the next inspectio Licensee representatives acknowledged the inspector's concein and
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committed to evaluate the adequacy of-its radiological control procedures and make upgrades, as appronriate. (Inspector Followup Item 50-20/90-01-01).
9.0 O censee Action on Previously Identified Items i
. Closed (50-20/78-06-03); Complete RSC review of ROR 78-03 and 78-04. The inspector verified by review of the RSC mee;ing minutes that these
- occurrences were reviewed at the full RSC meeting-of November 21, 1979, Clo' sed (50-20/79-01-01); Review calibration frequency of containment leak
- rate test (LRT) ~ meter. The licensee established an annual calibration frequency for.this mete This calibration is scheduled to occur before the annual containment leak rate test. The calibrations were performed by the-local natural gas company. The. inspector reviewed the March 29, 1990 calibration and found it to be satisfactor <
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. Closed (50-20/79-01-02); Review progress on installation of a new nuclear safety channel test signal generator. The inspector verified that the test signal generator was installed in the reactor console. The instrument is used to verify the nuclear safety channel scram trip setting Closed (50-20/79-01-03); RSC review of ROR 79-01. The inspector verified by review of the RSC meeting minutes that this occurrence was reviewed at
.the full RSC meeting of November 21, 197 Closed (50-20/79-01-04); Review RSC action with respect to the pre-opera-tional test for the Fatigue Cracking Jxperiment. Through review of experiment documentation and facility procedures, the inspector determined that, in accordance with PM 1.4, pre-operational tests of faci _lity equipment and/or experimental apparatus of this type are considered to be covered by a " Class B" procedure and, therefore, only required the approval of two licensed Senior Reactor Operators and the Director of Reactor Operations. PM 3.11.3, " Fatigue Cracking Experiment Start-up Checklist", was reviewed by the inspector and was found to contain the required approvals. .The inspector noted that the RSC, at its meeting of September 6,1978 reviewed the Safety Analysis Report for the Fatigue Cracking Experiment, dated August 13, 1978, and authorized a subccmmittee to -approve _ the experiment subject to resolution of several items. The subcommittee _ met several times to review and approve changes concerning the conduct'of this experiment. The inspector concluded that the experiment r3ceived the proper level of revie Closed (50-20/79-01-06); Review Safety Analysis Report (StA) to verify inclusion of new hot cell. The inspector reviewed safe'.y reviews for the hot cell' that involved installation, procedures for ue, and for
, possession and use in the hot cell of radioactive materials activated elsewhere. SAR Revision No. 20, dated February 6,1980, updated Section-3.2,3 and Chapter 10 of the SAR to include the reactor floor hot cel Closed (50-20/79-02-07); Brief operators to assure required logs are kept and determine at what operating level hourly log recording will commenc The. inspector reviewed PM l'.8, " Reactor Operating Logs", dated
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December 5, 1979. This PM stated when logs are to be taken and listed several exceptions to the general rul Closed (50-20/79-02-08); Add replacement of reactor tank water level probe insulation to the preventative maintenance schedule. The inspector verified that a requirement to inspect the insulation of the electrical conductance type reactor water level probe was added to PM 6.1.3.7-3. The inspector reviewed inspection records and verified that this inspection was performed until' the probe was replaced in 1985 with an improved typ I
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Closed (50-20/79-02-09); Review progress on reactor tank water level probe modification. The electrical conductance type reactor tank _ water level probe' was replaced on July 8,1985 with a float type probe. The inspector
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confirmed the existence of the probe by direct observation and also reviewed Quality Assurance Package M81-3 which reviewed and approved the modification to the facility to install the new prob , Closed (50-20/79-02-10); Review latest status of shipping of failed fuel off site for examination. In 1979, the licensee was considering shipping the fuel element 4M-10 off site for additional examination of a blister L that had developed on it. The licensee later believed that the defect was understood and decided against additional examination. The fuel element'. .
__ is still on site and no plans are being made to ship the element off site.
_ Closed (50-20/79-02-11); RSC review of ROR 79-02, 79-03, and 79-04. The
_ inspector verified by review of the R5C meeting minutes that these occurrences were reviewed at tha full RSC meeting of November 21, 1979.
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Closed (50-20/88-02-01); Review pressure generated in experiment in
' relation to technical specificatio:i The licensee calculated that the r maximum pressure spike that coulc be generated by the Pressurized Water Reactor Chemistry Loop (PCCL) experiment was 485 psi. The aluminum thimble had a " Proof Pressure" of 750 psi. This was lower than required by the Technical Specification for prototype testing, whir.h would require the " Proof Pressure" to be- twice the maximum expected pressure, which in this case was 970-psi. The inspector verified that additional testing
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occurred and that the prototype has been pressure tested to 1000 psi. The inspector also reviewed design changes that reduced the pressure spike in the final encapsulation to 50 ps _
Closed (50-20/87-03-01); Failure-ta post equipment room as an Airborne Radioactivity Area. During a tour of the MITR facility on September 19,_1990, the inspector observed that the entrance to the
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Equipment Room had been appropriately poste _
-10.0 Exit Interview The. inspectors met with the licensee's management (denoted in paragraph 1) at the conclusion of the Inspection'on September 20, 1990. The inspectors summarized the purpose and scope of the inspection and
_ findings as described in this report. Regarding the finding of a poorly i documented radiological control program and lack of written implementing procedures, the licensee's management stated that this matter would be evaluated and appropriate actions taken, r
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LOUTSTANDING ITEMS FILE SINGLE' DOCKET E'NTRY-FORM . ,
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REPORT HOURS L Operations X 7. Outages 2. Rad-Con- -X 8.. Training 3.' Maintenance- 9. Liceresing Docket N Io I o i 5 l o I a l o . Surveillance 10. QA 5. Emerg. Pre . Other Originator BJ.46(ST/A).
6. Sec/Safegrd .-Fire Protection /
Housekeeping- Reviewing Supervisor /2 - 6CE6S -
Item Number' Type SALP' Area Area Action ~Due Date Updt/C1sout Rpt/ Date M 17181-1C161-1c131 lul AJ 41 lolvi tJ 4AITir lotA4 4 lemtal Il l-1 l l-l l l l l l-l l 1-1 1 1 10171-1z1c1-191o1
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Originator / Modifier Resp Sec lAlolAlmlst i 1l l I 18 1 Descriptive Title clol rwi e - t it: T LI l etl sic l leI t' V i r I El al 10 1 Fl f (< l o l Rl l ~7101 - 1 o131 :AINIDI l l- ! i
'7 ls i -lo 1 s N I c' A Ll r 6l El /4 lTl I i O/V1 lFl(ziflOlMit NlC 4I olfl l l I I I I I c- o- Nif A ( N; m t n T- '
t i tl Al lc rzl AITIE l IMIEIT Elf?_ 1 1 I I I I I l l l 1 1 I I I I I I I I I I I I l 1 1 I I I I I I I Item Number Tm' SALP Area Area Action Due Date' Updt/Cisout Rpt/ Date M 17191-1c111-10121 ll: Fill lClfitlAIAITl/loid91 . 18!hPF#1 l l l-l l l-l l I l~l l-l l l-l l l Pl91-lZict-1914 gg MM DD YY DD .Y Y Originator / Modifier Resp Sec l A-I D l 41/)l S l _ l l l l l 141 Descriptive Title I R IE. l v i ; t; a Fi A Lo l e t /4 . E l s t_5 I I o! ml I /Lidls17 14 L<_lc14171/ olN' l o l 1:1 IN l EilNI I I INICc v t: Al c 5 A: fICTl41 IclH A I NI N ' ti Li IT f_l S ITI 15 llG :NI Alc- 1 I l- 1 I IGl tl N! t- tzl:A lr <D F-.11 1 I luI l l 1 I I I I l l l l l l l l- 1 I l l l l 1 1 Region I Form 6 (January 1987)
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t Report Hours: Enter report hours for each SALP area addressed in the inspection report.-
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Docket # - Insert 5 digit hyphenated, e.g. 50-219. or the 6 digit non hyphenated, e.g., 702011 docket number in the spaces provided, fteft Number - The first 5 spaces include a hyphen and are the same as the report number, e.g., 76 19. This portion of the item number is the same for all items identified in a given report and is only filled in once per page although WPC will enter this portion in all items on the page. The last two digits are assigned when documenting the item within a given report and start with 01 and continue sequentially until all items requiring followup have been 1 identifie _Typ_e - Enter the 3 letter code SLI through SLV to indicate nonceepliance severity leve H'. - Deviation. UNR - UhResolved. COF - Construction Deficiency Reports. Lil - Other Licensee Identified items (Note: matters identified by the licensee should be entered _o,n_il if there is safety or safety-guards significance requiring followup action). Inspector followup items are coced 1FI and are used when an item to be followed up does not fall in one cf the coding ,
categories above. NY4 and NVE - ho violation issued and Severity level 4 or I SALP Area: Enter the SALP area of the outstanding ite Area Code - Enter the 3 letter code that best characterizes the Functional Area into which the item would fal CEP - Construction Environment Protection PAC - Material Accountability / Control COA - Construction Quality Assurance OEP - Operations Environmental Protection CAS - Concrete and Structures 00A - Operations Quality Assurance FDP - Fire Detection / Prevention LRT - Leak Rate Testing FND - Foundations PNT - Maintenance 15! - Inservice Inspection POT - Pre 0peration Testing IST - Inservice Testiri, Pc s 1. Yches PSC - Procedures, St,rveillance. Calibratic NOT - honDestructive Testing REF - Refueling activities RVI - Reactor Yessel and Internals kFS - Reactor Fuel Shipping SNB - Snubbers TRN - Training )
SME - Special Mechanical / Electrical Problem EPP - Emergency Plans and Procedures ULO - WeL0ing IMV - Independent Measurements Van FFH - Fuel- Fabrication and Handling RDP - Radiation Protection FNS - Fuel Facility huclear Safety thV - INiestigations PMS - Prepara'lon of Materials for Shipment SPP - Security and Physical Prctection
! (used for fuel / reprocessing only) OTh - OTHer speciality, not coded elsewhere Resp - Enter the specific code which identifies the section with responsibiliy to perfonn inspection folloe u A. Materials Assurance Section 6. Division of Reactor Projects B. Quality Assurance Section H. Effluents Rad. Protection Section C. Test Programs Section 1. Facilities Rad. Protection Section D. Operational Programs Section J. Emergency Preparedness Section
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E. Materials and Processes Section K. Plant Protection Section F. Plant Systems Section ,
Action Due Date - Enter the date by which hRC followup should be completed. (Typically 3 months)
Update /Closecut Report # - The first 5 positions correspond to the report number. *4. 86 0 The position following the second hyphen is filled with a C" if the item was 'etnspected and Closed or was opened and closed witb% W same inspection. An "0" is inserted if the item was reinspected and remains Outst".iding.
l Date item was opened, modified or close Originator - Last name of individual establishing a new item.
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Modifier - Last name of individual making a modification to an existing ite Descriptive Title: A description of 123 or less characters, the module number may be included, if desire .
Region i Fonn 6 (Side 2)
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- OUTSTANDING ITEMS FILE-SINGLE DOCKET ENTRY FOR ,7
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REPORT HDURS -1. Operations -X 7 Outages
- 2. Rad-Con X .8.' Trainin . Maintenance '
9.: Licensin Docket N lo 15'l 017. I O!
4. Surveillance- 10. QA
'5. Emerg. Pre . Other . Originator M. ALLSD A)
6. Sec/Safegrd . Fire Protection / Reviewing Supervisor 4. &7fES Housekeeping Item Number Type SALP Area ' Area Action Due Date Updt/C1sout-Rpt/ Date l'1191-lolEl-lf ICl llllFill - lol9ltlel AlTl / lclM 51 l#14141 Il l-l l l-l l i l 1--l-l l l-l 1l lClol-lzlC1-1910 Originator / Modifier .
Resp Sec IklD I Almi s t i I I I i 141 Descriptive Title llK O V 1 W (AJ 9 THA Tl4151 I o f FI lolF IP ls il l Tlf-l l FitA I El L l 191RlIl FIF4f_INITl I l F 4 C' X A m! -l i i 'l i l i l i l i I l- I
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I I l i I I I l- 1 I I I I I I I I I I I I I I I I I Item Number- ' Type SALP Area Area Action Due Date Updt/C1sout Rrt/ Date
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Resp Sec 1AIDIAIMl91 I I I1 1 IHI-Descriptive Title Alls ! C 2. 6 U f ti uJ C Fl 'RIOll e_Il 1 7l 9 l -l 0121 :7 9 -
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Ifbtfel-Iclzi-loill la NFJ ICl H tl(44 Tl /lDirJ 9 lolTlHI I i 1-1 1 1-1 1 I l I l-l I l-l l i VJI'l-121Cl-191a MM DD YY MP DD Y Y:
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Descriptive Title lPi e! tl 1 - t; to el l t2 1/2 l!t. 5 Is la i/ElEl i F1/t to imi I el 71 pl L Ali : ml E-WI TIJ LTlol i TLSI l-
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I :1~ l I l' 1 l I I I I I I I I I I I I I I I I L i I! I I I L I l i I I i i I I I I I I I I I I l i I I I I Region I Form 6 (January 1987)
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Report Hours: Enter repor$ hours for each sal,P area addressed in the inspection repor .
Docket # Insert 5 digit hyphenated, e.g. 50-?!9, or the 6 digit non hyphenate '.
e.g., 702011, docket number in the spaces provide Item Number - The first $ spaces include a hyphen and are the same as the report number, e.g., 76-19. This portion of the item number is the same for all items identified in a given report and is only filled in once per page although WPC will enter this portion in all items on the page. The last two digits are assigned when documenting the item within a given report and start with 01 and continue sequentially until all items requiring followup have been identifie gTe Enter the 3 letter code SLI through SLV to indicate noncompliance severity leve w, - Deviation, UNR - UhResolved. CDF - Construction Deficiency Reports, LII - Other Licensee Identified items (Note: matters identified by the licensee should be entered _on_iy if there is safety or safety-guards significance requiring followup action). Inspector followup items are coced IFl and are used when an item 10 be fnllowed up does not fall in one of the coding categories above. NV4 and NVS - he violation iscued and Severity Level 4 or SALP Area: Enter the SALP area of the outstanding ite Area code - Enter the 3 letter code that best characterizes the Functio..al Area into which )
the item would f al CEP - Construction Environment Protection PAC - Material Accountability / Control COA - Construction Quality Assurance OEP - Operations Environmental Protection CAS - Concrete and Structures 00A - Operations Quality Assurance FDP - Fire Detection / Prevention LRT - Leak Fate Testing I FND - FouN0ations PNT - Ma1NTenance j 151 - Inservice Inspection POT - Pre 0peration Testin IST - In$ervice Testirc. Pu s & Whes PSC - Procedures, Strveil ance, Calibratiot NET - hon 0estructive Testing REF - Refueling activities !
RVI - Reactor Vessel and Internals RFS - Reactor Fuel Shipping SNB - Snubbers TRN - Training i SME - Special Mechanical / Electrical Problem EPP - Emergency Plans and Procedures WLD - Welding IMV - Independent Measurements Van FFH - Fuel Fabrication and Handling RDP - Radiation Protection FNS - Fuel Facility huclear Safety INV - INiestigations PHS - Preparation of Materials for Shipment SPP - Security and Physical Protection (used for fuel /reprocessin5 only) OTh - OTHer speciality, not coded elsewhere Resp - Enter the specific cooe which identifies the section with responsibiliy to perform inspection follow up.
l A. Materials Assurance Sectio G. Division of Reactor Projects B. Quality Assurance Section H. Effluents Rad. Protection Section C. Test Programs Section 1. Facilities Rad. Protection Section D. Operational Programs Section J. Emergency Preparedness Section E. Materials and Processes Section K. Plant Protection Section F. Plant Systems Section ,
Action Due Date - Enter the date by which NRC followup should be completed. (Typically 3 months; Update /Closecut Report # - The first 5 positions correspond to the report number, e.g., 86-0 The position following the second hyphen is filled with a "C" if the item was reinspected and Closed or was opened and clcsed within the same inspection. An "0" is inserted if the item
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l was reinspected and remains Outstanding.
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Date item was opened,imdified or close Originator - Last name of individual establishing a new ite Mod'ifier - Last name of individual making a modification to an existing ite Descriptive Title: A description of 123 or less characters, the module number may be included, if desire ,
Region i Fom 6 (Side 2)
(January 1987)
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OUTSTANDIE ITEMS FILE SIELE DOCKET ENTRY FORM
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REPORT' HOURS 1. Operations . Outages' _ "
2. Rad-Con' 8. Training
'V- 9. Licensing Docket N IO 101 Sl o12. lo l 3. Maintenance 4. Surveillance 10. Q Originator -/ k7. 4(457/ M'
5. Emerg. Pre . Othe . Sec/Safegrd . Fire Protection / Reviewing Supervisor d . tscr d 6 S Housekeeping SALP Area Area- Action Due Date Updt/Cisout Rpt/ Date W S d)
Ites Number T:rpe B191-I cizl-Ic171 lu Al ti lolM 44M Ti ticl49 l@gMdi_ l l l-l I l-l i I I I l-l I l-l i I lo!?l-lzici-lilo MM DD .Y Y MM .00 YY
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Resp Sec pg Originator / Modifier I AI D I Al /v1 S I l l l 1 l- -lH I Descriptive Title Gi u lI l E IE lo i IL- 1 Of GIS I 1 'l I 6: R C (; olF ' t VL Al T: oltz.f 31 iTlol I K IE-Iti v i 1 41 I I I I I I I I I -l I i i i l I i l1 l 1 l i I I I I I i
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l I 1 I l- l l l 1 Area Action Due Date Updt/Cisout Rpt/ 4Wte Ites Number T'rpe :SALP Area lo 191-l zi ci-19 to.
l'7141-Icizl-lCl81 lu N14 - Iml AlilN Ti th14f N1cl IP1 Nil MM I i l-l 0Di 1-1YYI i i i 1-1 I l-1 I l-MM DD .Y Y Originator / Modifier' Resp Sec l AIDI Almis l l l l l l lH I Descriptive Title IT o I j 14 t F G A- C1 tum ti eJi 7: ICLFl n PIRio lr$1E l I/ I N1 5 L u i (-lA Tl / lolNI A!:D D' i l i I I I I I I I I I I I I I S H e o a L. E- I i i Fil/h l s l l l 1 I l- 1 I I I I I I I I I l ! I i 1 l _I I I Area Action Due Date__ Updt/C1sout Rpt/ Dateasseth Item Number T3rpe SALP Area lot 71-izlct-lyn laptpl l I l-l I l-l I i i i 1-l I l-l i I 17141-Ict 21-Icl91 if Fl f l IA1All lN Tit 1/4Hici Originator / Modifier Resp Sec I A l ol Al /hl S i i !l i I I tt i Descriptive Title 021 El Alc-lT Ol El ITI 4' N: #1 0 l l !
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tv1 o Ol i IPll L c_ ' AllT 'il o INI lol Fl l i I i i i U l l i I E V 6 Cl IWA O; @ 6. i i i i i i i I lw Al TLE #- C'
I -l i I I I I ! I I I I H I l 1 I I I E I Il 1 -l :l l 'I 1 I I Region I Form 6 (!anuary 1987) .
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Report bours: Enter report hours for each SALP area addressed in the inspection repor Docket d - Insert 5 digit hyphenated, e.g. 50 219, or the 6 digit non-hyphenated, e.g., R20ll, docket number in the spaces provide Itee Number - The first 5 spaces include a hyphen and are the same as the report number, e.g., M-1 This portion of the item number is the same for all items identified in a given report and is only filled in once per page although WPC will enter this portion in all items on the page. The last two digits are assigned when documenting the item within a given report and start with 01 and contir.ue sequentially until all itens reovirint, followup have been identifie gi >e - Enter the 3 letter coce SLI through SLV to indicate noncompliance severity leve LL, - Deviation, UNR - UEResolved CDF Construction Deficiency Reports Lil - Other Licensee Identified items (Note: matters identified by the licensee should be entered goni if there is safety or safety-guards significance requiring followup action), inspector followup items are coced IFI and are used when an item to be followed-up does not fall in one of the coding
categories above. NV4 and NYS - ho violation issued and Severity Level 4 or SAtp Area: Enter the SALP area of the outstanding ite Area Code - Enter the 3 letter code that best characterizes the Functional Area into which i the item would fal CEP - Construction Environment Protection PAC - Material Accountability / Control COA - Construction Quality Assurance OEP - Operations Environmental Protection CAS - Concrete and Structures 00A - Operations Ouality Assurance FDP - Fire Detection / Prevention LRT - Leak Rate Testing FND - foundations FNT - Maintenance 151 - Inservice Inspection POT - Pre 0peration Testing IST - Inservice Testir{, Pms 1. Yches PSC - Procedures Surveillance, Calibretie NCT - honDestructive Testing REF - Refueling activities RV1 - Reactor Vessel and Internals kFS - Reactor fuel Shipping SNB - Snubbers TRN - Training )
SME - Special Mechanical / Electrical Problem EPP - Emergency Plans and Procedures WLD - Welding IMV - Independent Measurements Van FFH - Fuel Fabrication and Handling RDP - Radiation Protection FNS .. Fuel facility huclear Safety INV - INiestigations PMS - Preparation of Materials-for Shipment SPP - Security and Physical Protection (used for fuel /reprocesstr5 only) OTH - OTHer speciality, not coded elsewhere Resp - Enter the specific cooe which identifies the section with responsibiliy in perform inspection follow u A. Materials Assurance Section 6. Division of Reactor Projects B. Quality Assurance Section H. Effluents Rad. Protection Section C. Test Programs Section 1. Facilities Rad. Protection Section D. Operational Programs Section J. Emergency Preparedness Section E.. Materials and Processes Section K. Plant Protection Section F. Plant Systems Section ,
. Action Due Date - Enter the date by which NRC followup should be completed. (Typically.3 months)
Update /Closecut Report # - The first 5 positions correspond to the report number, e.g., 86-0 The position following the second hyphen is filled with a *C" if the item was reinspected and Closed or was opened and closed within the same inspection. An "0" is inserted if the item was reinspected and remains Outstandin Date item was opened, modified or close Originator - Last name of individual establishing a new ite , Mod'ifier - Last name of individual making a modification to an existing ite Descriptive Title: A description of 123 or less characters, the module number may be included, if desire ,
Region 1 Fonn 6 (Side 2)
(January 1987)
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DUTSTANDING ITEMS filii SINGLE DOCKET ENTRY FOR , ;:,
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i REPORT HOURS 1. Operations X~ 7. Outages 2. Rad-Con: )( 8. Training
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-3. Maintenance 9. Licensing Docket N I o I of 5'l o i 2- I Cl 4. Surveillance 10. QA 5. Emerg. Pre . Other Originator #1. 4RS7h)
.6. Sec/Safegrd . Fire Protection /. Reviewing Supervisor /2. 6026$
Housekeeping-Item Number Type SALP Area- -Area Action Due Date Updt/C1sout Rpt/
l'Il91-lCl l l-lCl 31 lu Wiki lolpitt/21 AITl r icir451 lelilies91 1-1-1-1 l l-l l l _i_l l-l l l-l l l 10191-12101-1710 Originator / Modifier Resp Sec og MM _D D YY MM DD YY, I A I D I Altvll s i l- 1 l -l I 181 ,
Descriptive Title
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it 5- cl / t/ I 6 M io L Fl if.l<31 El 17 lci 1 -l cl i I l l l 1 l 1 l i l i l i I- I l- l'
H I l 1 1 I I l- I l- 1 I I I I l I I I l l l l 1 1 I I I I J L 4 l l 1 I l- 1 l l l 1 1 I I I l I i l l I l l l I I i l 1 i'
Item Nur6er Tjrpe SALP' Area Area Action Due Date Updt/C1sout Rpt/ Date M 17141-i cll l-lCl41 if . lolp1014B ITl/ loir 4 31 l l l-l I l-l i I l l l-l l l-l l l 1C191-1Z141-1710, Fill l@%4dl MM DD YY MM DD YY'
OTH Originator / Modifier Resp Sec 1 Al bl A lmlSi 'l 1l I l l H i-Descriptive Title l El s c : A c T I ollra o M i el el C - l cl pl i Tl El S 171 i FlOl RI l FI Al TH I IGH Ml El -1 I JEl/L A C K- / N G E K P t Eli M t NIT l
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I I I I I I I I I I I H I I I I l [ :
l l l l 1 l i I I l- I l l I I I I I I I I Item Number Trpe SALP Area Area Action Due Date Updt/Ciscut Rpt/ 'Date M 17191-lci/l-lcidi cjf Fil l ICIFlti/2lplgl,Ic;e451 lggggpgg l l l-l l l-l l l l l l-l l l-l l l Icl91-lzlcq -lcylo, MM DD YY MM DD 'If Y
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Originator / Modifier ~ Resp Sec IAIDIAltl51 k 1 1 -l i l IH I Descriptive Title IR E Wll S E_ GlM E! HThol lIll/W CILI Ml O N l edl 6lw1 Hlo; TI IICI EIL l u '
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I U l i 1 1 l i I I I l 1 1 I I H I I I Region I Form 6 (January 1987)
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Report Hours: Enter report hours for each SALP area addressed in the inspection repor ,
Docket # fnsert 5 digit hyphenated, e.g. 50 219. or the 6 digit nonohyphenated, . docket number in the spaces provided.
Itet Number - The first ! spaces include a hyphen and are the same as the report number.
e.g., 76-19. This portion of the item number is the same for all items identified in a given report and is only filled in once per page although WPC will enter this portion in all items on the pag The last two digits are 4551gned when documenting the item within a given report and start with 01 and continue sequentially until all items requiring followup have been l identified.
2v T e - Enter the 3 letter code SLI through SLV to indicate noncompliance severity level.
IU - Deviation. UNR - UhResolved. COE - Construction Deficiency Reports. Lil - Other Licensee Identified items (Note: matters identified by the licensee should be entered Joni if there is
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safety or safety-guards significance requiring followup action). Inspector followup items are coced IFl and tre used when an item to be followed up does not fall in one of the coding categories above. NV4 and NV5 - ho violation issued and Severity Level 4 or 5.
SALP Area: Enter the SALP area of the outstanding item.
01 Area Code - Enter the 3 letter code that best characterizes the functional Area into which tne item would fal PAC - Material Accountability / Control CEP - Construction Environtrent Protection OEP - Operations Environmental Protection COA - Construction Quality Assurance CAS - Concrete and Structures 00A Operations Ouality Assurance FDP - Fire Detection / Prevention LRT - Leak Fate Testing FND Foundations PNT - Maintenance
!!! - Inservice Inspection POT - Pre 0peration Testing IST - Inservice Testir.:. Pu- s & Whes PSC - Procedures. Surveillance. Calibratiet NE' - hon 0estructive Testing REF_- Refueling activities RVI - Reactor Yessel,and Internals kFS - Reactor Fuel Shipping SNB - Snubbers TRN - Training i SME - Special Mechanical / Electrical Problem ePP - Emergency Plans and Procedures WLD - Welding IMY - Independent Measurements Van FFH - Fuel Fabrication and Handling 00P - Radiation Protection FNS - Fuel Facility huclear Safety INV - Investigations PHS - Preparation of Materials for Shipment SPP - Security and Physical Protection (used for fuel / reprocessing only) OTH - OTHer speciality, not coded elsewhere Resp - Enter the specific cooe which identifies the section with responsibiliy to perform inspection follow u A. Materials Assurance Section 6. Division of Reactor Projects B. Quality Assurance Section H. Effluents Rad. Protection Section C. Test Programs Section 1. Facilities Rad. Protection Section D. Operational Programs Section J. Emergency Preparedness Section E. Materials and Processes Section K. Plant Protection Section F. Plant Systems Section ,
Action Oue Date - Enter the date by which NRC followup should be completed. (Typically 3 months)
Update / Closeout Report # - The first 5 positions correspond to the report number, e.g., 86-0 The position following the second hyphen is filled with a *C" if the item was reinspected and Closed or was opened and closed within the same inspection. An "0" is inserted if the item was reinspected and remains Outstandin Date item was opened modified or close Originator - Last name of individual establishing a new ite Mod'ifier - Last name of individual making a modification to an existing ite Descriptive Title: A description of 123 or less characters, the module number may be include if desire .
Region 1 Fonn 6 (Side 2)
(January 1987)
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OUTSTANDING-ITEMS FILE SINGLE DOCKET ENTRY FORM 1 .- -
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REPORT HOURS 1. Operations- 7.-Outages-2. Rad-Con X 8. Training Docket ido.- 1 o lo 151 olz lo t-3. Maintenance 9. Licensing- '
4. Surveillance 10. QA _ Originator- /h. 414(57/ A)
5.~_Emerg. Pre . Other'
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6. Sec/Safegrd . Fire Protection / Reviewing Supervisor Housekeeping SALP Area Area _ Action Due Date Updt/Cisout Rpt/ ' ~Date M sD Item Number . Tupe i I l-l I l-1 I l ~ l I l-l 1 -1-1 1 -l D RI-12 bi-Filo lel71-lol31-lollt IS : Lit 41 litlAlolciclNI I i l l It21DIPl M ?? DD YY MM DD- YY Originator / Modifier " Resp Sec I A I U l5 IT ll-l MI' l l l l lHI Descriptive Title l i I (Al /4. E- T' o iFL cl 41 Tl l ElG I (Al i 1/'l/H EI A.;l 71 1/El ol ol/hl IA5I i 'l F-l I
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I I I I I l'9 I I I I I I I i ,
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Type SALP Area Area Action Due Date Updt/Ciscut Rpt/ Dat h Item Number IrJ AlolciciA1 1 I I i 1/4f DIPl i I l-1 I l-1 I I i i 1-1 I l-1-1 1 1o191-1z191-1910 191C1-16111-10111 lI Ti ll MM DD Y-Y MM DD YY Originator / Modifier Resp Sec itllu f s lTi r INI l l i I IHI Descriptive Title
/4 D tLAI T: 1-1 oi rv i IFlgslol-fl61Cl Elrlol M P itz t lGI E' Alml i I L. LAllC! /C O' F i I I I I I i I l i I I l p su o c t b a e E S u I I l l l l l l l l l l l l 1 1 I I I 1 ! I I l i
Action Due Date Updt/C1sout Rpt/ Date 0/M/Cisd SALP Area Area Ites Number T ye tl I I l- l l l l l l 11Il l l l-l l l-l I l- I l l-l I l-l I I .IMM l l-l I~I-I DD IYY ll l-l l l-l l l l l l DD YY MM Originator / Modifier Resp Sec
' ' ' ' ' ' Descriptive Title I L I i l 1: I l 'l l I I
- l -l I I I H I l !
i l I l l I I l l l I I I I I i l i i ! L l l I I l' I I I I I I l- 1- H I l 'I U I I I I I L l- -1 I ,
Region I Form 6 (January 1987)
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Report Hours: Enter report hours for each SALP area addressed in the inspection report, ,,
Docket # - Insert 5 digit hyphenated, e.g. 50-219 or the t digit non-hyphenated, l
e.g., a2oll, docket number in the spaces provide _
Itet Number -: The first 5 spaces include a hyphen and are the same as the report number, i
e.g., 76-19. This portion of the item number is the same for 511 items identified in a givttn report and is only filled in once per page although WPC will enter this portion in all items
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on the page. The last two digits are assigned when documenting the item within a given report i and start with 01 and continue sequentially until all items requiring followup have been identifie T Enter the 3 letter coce SLI through SLY to indicate noncompliance severity leve !
- L Jp OtVittion,
- UNR - UEResolved. C0F - Construction Deficiency Reports, Lil - Other Licensee Identifisd items (Note: matters identified by the licensee should be entered Jon1 if there is
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I safety or safety guards significance requiring followup action). Inspector followup items are coc0d IFl and are used when an item to be followed up does not fall in one of the coding C&tegories above. NV4 and NVS - ho violation issued and Severity Level 4 or SALP Area: Enter the SALP area of the outstanding ite I 01 Area Coos - Enter the 3 letter code that best characterizes the Functional Area into which the item would fal CEP - Centcruction Environment Protection PAC - Material Accountability / Control C0a - M u truction Quality Assurance OEP - Operations Environmental Protection i CAS - Concrete and Structures 00A - Operations Quality Assurance FDP - Fire Detection / Prevention LRT - Leak Fate Testirg FND - Foundations FKT - Maintenance .
151 - Inservice Inspection POT-Pre 0perationTestinkance,Calibratie IST - Inservice Testird, Pu~s 1. Yches PSC - Procedures, St,rveil 6 M1 - Nondestructive Testing REF - Refueling activities RV1 - Reactor Vessel and Internals kFS - Reactor Fuel Shipping SNB - Scabbers TRN - TFeiNing )
SME - Special Mechanical / Electrical Problem EPP - Emergency Plans and P- m dures W O - WeL0ing- IMY - Independent Measurements Van FFH - Fuel Fabrication and Handling RDP - Radiation Protection FNS - Fuel Facility huclear Safety INV - INiestigations PMS - Preparation of Materials for Shipment SPP - Security and Physical Protection (used for fuel / reprocessing only) OTh - OTHer speciality, not coded elsewhere Resp - Enter the specific coce which identifies the section with responsibiliy to perform inspection follow-u i A. Materials Assurance Section G. Division of Reactor Projects B. Quality Assurance Section H. Effluents Rad. Protection Section C. Test Programs Section 1. Facilities Rad. Protection Section D. Operational Programs Section J. Emergency Preparedness Section l E. Materials and Processes Section K. Plant Protection Section F. Plant Systems Section ,
Action Oue Date - Enter the date by which NRC followup should be completed. (Typically 3 months)
Uodate/Closecut Report 9 - The first 5 positions correspond to the report number, e.g., 86-0 The-position following the second hyphen is filled with a "C" if the item was reinspected and Closed or was opened and closed within the same inspection. An "0" is inserted if the item was reinspected and remains Outstandin Date item was opened, modified or close Originator - Last name of individual establishing a new ite Mod'ifier - Last name of individual making a modification to an existing ite Descriptive Title: A description of 123 or less characters, the module number may be included, if desire F Region 1 Forin 6 (Side 2)
1 (January 1987)
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